Computational fluid dynamic analysis of a closure head penetration in a pressurized water reactor [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1995.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- pages 696-710 : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- ALLOY 600 has been used typically for penetrations through the closure head in pressurized water reactors because of its thermal compatibility with carbon steel, superior resistance to chloride attack and higher strength than the austenitic stainless steels. Recent plant operating experience with this alloy has indicated that this material may be susceptible to degradation. One of the major parameters relating to degradation of the head penetrations are the operational temperatures and stress levels in the penetration.
- Report Numbers
- E 1.99:nureg/cp--0142-vol.1
E 1.99: conf-950904--vol.1
conf-950904--vol.1
nureg/cp--0142-vol.1 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
09/01/1995.
"nureg/cp--0142-vol.1"
" conf-950904--vol.1"
"TI95017077"
7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995.
Forsyth, D.R.; Schwirian, R.E.
View MARC record | catkey: 14364891